GB1107384A

GB1107384A – Nuclear reactor fuel elements
– Google Patents

GB1107384A – Nuclear reactor fuel elements
– Google Patents
Nuclear reactor fuel elements

Info

Publication number
GB1107384A

GB1107384A
GB35424/64A
GB3542464A
GB1107384A
GB 1107384 A
GB1107384 A
GB 1107384A
GB 35424/64 A
GB35424/64 A
GB 35424/64A
GB 3542464 A
GB3542464 A
GB 3542464A
GB 1107384 A
GB1107384 A
GB 1107384A
Authority
GB
United Kingdom
Prior art keywords
fuel
chamber
gas
pin
casing
Prior art date
1964-08-28
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)

Expired

Application number
GB35424/64A
Inventor
John Andrew Gatley
John Webb
Reginald Robert Gallie
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)

UK Atomic Energy Authority

Original Assignee
UK Atomic Energy Authority
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
1964-08-28
Filing date
1964-08-28
Publication date
1968-03-27

1964-08-28
Application filed by UK Atomic Energy Authority
filed
Critical
UK Atomic Energy Authority

1964-08-28
Priority to GB35424/64A
priority
Critical
patent/GB1107384A/en

1965-08-20
Priority to GB35932/65A
priority
patent/GB1114696A/en

1965-08-23
Priority to US481815A
priority
patent/US3357893A/en

1965-08-25
Priority to FR29406A
priority
patent/FR1448375A/en

1965-08-27
Priority to DE1514977A
priority
patent/DE1514977C3/en

1965-08-27
Priority to BE668870A
priority
patent/BE668870A/xx

1968-03-27
Publication of GB1107384A
publication
Critical
patent/GB1107384A/en

1968-05-15
Priority to FR151886A
priority
patent/FR94436E/en

Status
Expired
legal-status
Critical
Current

Links

Espacenet

Global Dossier

Discuss

Classifications

G—PHYSICS

G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING

G21C—NUCLEAR REACTORS

G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements

G21C3/02—Fuel elements

G21C3/04—Constructional details

G21C3/041—Means for removal of gases from fuel elements

G—PHYSICS

G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING

G21C—NUCLEAR REACTORS

G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements

G21C3/02—Fuel elements

G21C3/04—Constructional details

G—PHYSICS

G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING

G21C—NUCLEAR REACTORS

G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements

G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit

G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements

G21C3/3213—Means for the storage or removal of fission gases

Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS

Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE

Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION

Y02E30/00—Energy generation of nuclear origin

Y02E30/30—Nuclear fission reactors

Abstract

1,107,384. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY.’ 12 Aug., 1965 [28 Aug., 1964], No. 35424/64. Heading G6C. A vented fuel element has a vent path of extended length for promoting by delay the decay of short-lived gaseous fission products before they are discharged into fluid coolant contacting the element. Such an element for use in a liquid metal-cooled fast reactor comprises, as shown in Fig. 1B, an assembly of elongated fuel pins 11 housed within an open-ended hexagonal casing 12. The fuel pin sheathing is of stainless steel and the fuel a U0 2 /PuO 2 mixture. Two superposed gratings 13, 14 are located at the lower end of the casing 12, one set of alternate rows of pins 11 being brazed into one of the gratings while the other set are brazed into the other grating. Passing through each of the grating bars is a passage 16 which connects the interiors of the corresponding row of fuel pins with an annular chamber adjacent the casing 12 which in turn is connected by a gas entry bore to a collector chamber 17 formed by a sleeve 18 extending coaxially inside the lower end of the casing 12. A vent tube 23 extends upwardly from the bottom of the collector chamber 17 through the grating 13 to occupy one position of the fuel pin lattice. Above the fuel pin lattice, the vent tube 23 continues into an upper fixture joined to the casing 12 by legs leaving space for the discharge of coolant from the casing 12. On charging the fuel element into the reactor core, the coolant being under pressure to some extent in the region of the upper fixture will enter through holes in the latter into a gas trap chamber and if the initial gas content of the element remains cool, compression of such gas allows the coolant to reach the collector chamber 17 and form a free surface therein. When the initial gas content is raised in temperature corresponding to on-load operation of the reactor, the expansion of the gas expels coolant from the vent tube 23 and the gas trap chamber. Thereafter, gas liberated by the fuel material during operation finds its way through the passages 16 of the gratings 13, 14 to the collector chamber 17 and from there can ultimately escape to the surrounding coolant through the vent tube 23 and the gas trap chamber. The chief difference in a second embodiment lies in the construction of the collector chamber 17. Outer and inner concentric sleeves having a small clearance between them are disposed in the chamber 17 to form a labyrinth between the gas entry bore and the vent tube 23. A pool of sodium is introduced into the bottom of the delay space to immerse the lower end of the outer sleeve and so form a dip seal. This is effective to retain any Cs occurring as a decay product. Other liquids may be used to arrest a wider range of decay products. In a third embodiment, as shown in Fig. 3, a fuel element for a gas-cooled thermal reactor comprises a cluster of pins each comprising stacked pellets 41, 42 of slightly enriched U0 2 . At the lower end of the pin, an end cap 43 is separated from the pellet stack by two Al 2 O 3 discs 44, 45 while at the upper end there is only one Al 2 O 3 disc 46, a chamber 47 formed as an extension of the end cap 48 taking the place of the second disc and having open communication with the fuel-containing space through a hole 49. A length of capillary tube 50 longer than the overall length of the pin is coiled helically within the chamber 47. One end of the tube 50 is within the chamber 47 while the other projects externally of the pin and is sealed by brazing in passage through the end cap. Alternatively, the tube could extend along the fuel axis as a spine from one end of the fuel-containing space to the other and be open to this space at one end and open to the exterior of the pin at the other.

GB35424/64A
1964-08-28
1964-08-28
Nuclear reactor fuel elements

Expired

GB1107384A
(en)

Priority Applications (7)

Application Number
Priority Date
Filing Date
Title

GB35424/64A

GB1107384A
(en)

1964-08-28
1964-08-28
Nuclear reactor fuel elements

GB35932/65A

GB1114696A
(en)

1964-08-28
1965-08-20
Improvements in nuclear fuel elements

US481815A

US3357893A
(en)

1964-08-28
1965-08-23
Vented nuclear reactor fuel element

FR29406A

FR1448375A
(en)

1964-08-28
1965-08-25

Fuel cartridges for nuclear reactors

DE1514977A

DE1514977C3
(en)

1964-08-28
1965-08-27

Vented fuel element for nuclear reactors

BE668870A

BE668870A
(en)

1964-08-28
1965-08-27

FR151886A

FR94436E
(en)

1964-08-28
1968-05-15

Fuel cartridges for nuclear reactors.

Applications Claiming Priority (1)

Application Number
Priority Date
Filing Date
Title

GB35424/64A

GB1107384A
(en)

1964-08-28
1964-08-28
Nuclear reactor fuel elements

Publications (1)

Publication Number
Publication Date

GB1107384A
true

GB1107384A
(en)

1968-03-27

Family
ID=10377557
Family Applications (2)

Application Number
Title
Priority Date
Filing Date

GB35424/64A
Expired

GB1107384A
(en)

1964-08-28
1964-08-28
Nuclear reactor fuel elements

GB35932/65A
Expired

GB1114696A
(en)

1964-08-28
1965-08-20
Improvements in nuclear fuel elements

Family Applications After (1)

Application Number
Title
Priority Date
Filing Date

GB35932/65A
Expired

GB1114696A
(en)

1964-08-28
1965-08-20
Improvements in nuclear fuel elements

Country Status (4)

Country
Link

US
(1)

US3357893A
(en)

BE
(1)

BE668870A
(en)

DE
(1)

DE1514977C3
(en)

GB
(2)

GB1107384A
(en)

Cited By (2)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

GB2163888A
(en)

*

1984-08-30
1986-03-05
Atomic Energy Authority Uk
Fission gas plenum chamber for nuclear fuel element sub-assembly

GB2163889A
(en)

*

1984-08-30
1986-03-05
Atomic Energy Authority Uk
Fuel assembly

Families Citing this family (13)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

US3432388A
(en)

*

1967-06-09
1969-03-11
Atomic Energy Commission
Nuclear reactor system with fission gas removal

US3625823A
(en)

*

1968-07-09
1971-12-07
Babcock & Wilcox Co
Nuclear fuel rod

US3459636A
(en)

*

1968-07-24
1969-08-05
Atomic Energy Commission
Vented fuel pin

US3627635A
(en)

*

1968-09-23
1971-12-14
Gen Electric
Nuclear fuel retainer

US3953288A
(en)

*

1970-03-24
1976-04-27
The United States Of America As Represented By The United States Energy Research And Development Administration
Gas venting

US4678627A
(en)

*

1985-04-04
1987-07-07
Westinghouse Electric Corp.
Debris-retaining trap for a fuel assembly

US8929505B2
(en)

*

2009-08-28
2015-01-06
Terrapower, Llc
Nuclear fission reactor, vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system

US8712005B2
(en)

*

2009-08-28
2014-04-29
Invention Science Fund I, Llc
Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system

US9269462B2
(en)

2009-08-28
2016-02-23
Terrapower, Llc
Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system

US8488734B2
(en)

*

2009-08-28
2013-07-16
The Invention Science Fund I, Llc
Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system

US20110150167A1
(en)

*

2009-08-28
2011-06-23
Searete Llc, A Limited Liability Corporation Of The State Of Delaware
Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system

TWI480887B
(en)

*

2012-10-30
2015-04-11
Atomic Energy Council
Fluid-discharging device less-stirring liquid in fuel pool

JP2022530665A
(en)

*

2019-04-30
2022-06-30
ウェスティングハウス エレクトリック カンパニー エルエルシー

General PLENUM fuel assembly design to help facilitate refueling in compact containers, long life cores, and POOL reactors

Family Cites Families (1)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

US3238105A
(en)

*

1964-06-03
1966-03-01
Malcolm J Mcnelly
Fuel element assembly for a nuclear reactor

1964

1964-08-28
GB
GB35424/64A
patent/GB1107384A/en
not_active
Expired

1965

1965-08-20
GB
GB35932/65A
patent/GB1114696A/en
not_active
Expired

1965-08-23
US
US481815A
patent/US3357893A/en
not_active
Expired – Lifetime

1965-08-27
BE
BE668870A
patent/BE668870A/xx
unknown

1965-08-27
DE
DE1514977A
patent/DE1514977C3/en
not_active
Expired

Cited By (2)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

GB2163888A
(en)

*

1984-08-30
1986-03-05
Atomic Energy Authority Uk
Fission gas plenum chamber for nuclear fuel element sub-assembly

GB2163889A
(en)

*

1984-08-30
1986-03-05
Atomic Energy Authority Uk
Fuel assembly

Also Published As

Publication number
Publication date

GB1114696A
(en)

1968-05-22

DE1514977A1
(en)

1969-07-17

DE1514977B2
(en)

1974-02-14

US3357893A
(en)

1967-12-12

DE1514977C3
(en)

1974-09-19

BE668870A
(en)

1966-02-28

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(en)

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Diving bell type control rod equipped with sodium inflow port

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